|
|
|
| Effect of Sn Content on Corrosion Resistance of N36 Alloys in LiOH Aqueous Solution |
| YANG Zhongbo, ZHAO Wenjin, MIAO Zhi |
| Science and Technology on Reactor Fuel and Materials Laboratory，Nuclear Power Institute of China (NPIC) ，Chengdu 610041, China |
|
|
|
|
Abstract Abstract：The corrosion resistance of N36(Zr-1Sn-1Nb-0.3Fe) and low-tin N36(Zr-0.8Sn-1Nb- 0.3Fe) alloys were studied in 0.03 mol/L LiOH equous solution at 360 ℃ as well as 18.6 mol/L Pa pressure. The results show that the corrosion transition of N36 specimens appears earlier than that of low-tin N36 and the weight gain of N36 specimens is higher than that of low-tin N36 after the corrosion transition. The cracks paralleling to the interface of oxide/metal are formed in the fracture surface of the oxide film and the oxide film in the inner surface appears at the“Cauliflower-like” morphology . With the increasing of corrosion rate ，there are more cracks in the fracture surface of the oxide film and the size of “cauliflower-like”structure grows bigger. It was concluded that the crackss were related to the t-ZrO2 and the solid solution contents of Sn in α-Zr will be responsible for the difference of corrosion resistance for N36 and low-tin N36．
|
|
|
|
|
[1] Zhao W J, Liu Y Z, Jiang H M, et al. Effect of heat treatment and Nb and H contents on the phase transformation of N18 and N36 zirconium alloys [J]. J. Alloys Compd., 2008, 46(2): 103-108
[2] Liu J Z, Zhao W J, Xue X Y, et al. Nuclear Structure Materials [M]. Beijing:Chemical Industry Press, 2007
(刘建章, 赵文金, 薛祥义等. 核结构材料 [M]. 北京: 化学工业出版社, 2007)
[3] Garde A M, Comstock R J, Pan G, et al. Advanced zirconium alloys for PWR application [J]. J. ASTM Int., 2010, 7(9): 1546-1568
[4] Yueh H K, Kesterson R L, Comstock R J, et al. Improved ZIRLOTM cladding performance through chemistry and process modifications [J]. J. ASTM Int., 2005, 2(6): 330-346
[5] Shishov V N, Peregud M M, Nikulina A V, et al. Structure-phase state, corrosion and irradiation properties of Zr-Nb-Fe-Sn system alloys [J]. J. ASTM Int., 2007, 5(3): 724-743
[6] Park J Y ,Yoo S J , Choi B K ,et al. Corrosion and oxide characteristics of Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr alloys in 360 ℃ pure equous and LiOH solution [J]. J. Nucl. Mater., 2008, 37(3): 343-350
[7] Zhou B X, Li Q, Yao M Y, et al. Microstructure evolution of oxide films formed on zircaloy-4 during autoclave tests [J]. Nuclear Power Eng., 2005, 26(4): 364-371
(周邦新, 李强, 姚美意等. 锆-4合金在高压釜中腐蚀时氧化膜显微组织的演化 [J]. 核动力工程, 2005, 26(4): 364-371
[8] Yao M Y, Zhou B X, Li Q, et al. A superior corrosion behavior of Zircaloy-4 in lithiated equousat 360 ℃/18.6 MPa by β-quenching [J]. J. Nucl. Mater., 2008, 374: 197-203
[9] Zhang H X, Fruchart D, Hlil E K, et al. Crystal structure, corrosion kinetics of new zirconium alloyss and residual stress analysis of oxide films [J]. J. Nucl. Mater., 2010, (396): 65-70
[10] Takeda K, Anada H. Mechanism of corrosion rate degradation due to tin [J]. J. ASTM Int., 2000: 592-608
[11] Zhao W J, Miao Z, Jiang H M, et al. Corrosion behavior of Zr-Sn-Nb alloy [J]. J. Chin. Soc. Corros. Prot., 2002, 22(2): 124-128
(赵文金, 苗志, 蒋宏曼等. Zr- Sn-Nb 合金的腐蚀行为研究 [J]. 中国腐蚀与防护学报, 2002, 22(2): 124-128
[12] Kim H G, Baek J H, Kim S D, et al. Microstructure and corrosion characteristics of Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr alloy with a β-annealing [J]. J. Nucl. Mater., 2008, 372: 304-311
[13] Park J Y, Yoo S J, Choi B K, et al. Oxide microstructures of advanced Zr alloys corroded in 360 ℃ water loop [J]. J. Alloys Compd., 2007, 437: 274-279
[14] Yilmazbayhan A , Breval E, Motta A T, et al. Transmission electron microscopy examination of oxide layers formed on Zr alloyss [J]. J. Nucl. Mater., 2006, 349: 265-281
[15] Zhou B X, Li Q, Liu W Q, et al. The effects of water chemistry and composition on the microstructure evolution of oxide films on zirconium alloys during autoclave tests [J]. Rare Met. Mater. Eng., 2006, 35(7): 1009-1016
(周邦新, 李强, 刘文庆等. 水化学及合金成分对锆合金腐蚀时氧化膜显微组织演化的影响 [J]. 稀有金属材料与工程, 2006, 35(7): 1009-1016）
[16] Moyal J S, Diazi M, Bartolome J F, et al. Zirconium oxide film formation on zircaloy by equous corrosion [J]. Acta Mater., 2000, (48): 4749-4754
[17] Motta A T, Yilmazbayhan A, Comstock R J, et al.Microstructure and growth mechanism of oxide layers formed in Zr alloys studied with micro beam synchrotron radiation [J]. J. ASTM Int., 2005, (2): 205-232
[18] Bossis P, Thomazet J. Study of the mechanisms controlling the oxide growth under irradiation:characterization of irradiated Zr-4 and Zr-1Nb-O oxide scales [J]. J. ASTM Int., 2002, 6(4): 190-221
[19] Anada H, Herb B J, Nomoto K I, et al. Effect of annealing temperature on corrosion behavior and ZrO2 microstructure of zircaloy-4 cladding tube [J]. J. ASTM Int., 1996, 74-93
[20] Qin W, Nam C, Li H L, et al. Tetragonal phase stability in ZrO2 film formed on zirconium alloys and its effects on corrosion resistance [J]. Acta Mater., 2007, (55): 1695-1701
|
| No Suggested Reading articles found! |
|
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
| |
Shared |
|
|
|
|
| |
Discussed |
|
|
|
|
